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Sakai, Akihiro; Okoshi, Minoru
Radiation Risk Assessment Workshop Proceedings, p.175 - 186, 2003/00
To establish the clearance levels, the Nuclear Safety Commission (NSC) has been discussing the clearance levels since May 1997. The NSC derived the unconditional clearance levels for the solid materials, namely concrete and metal, arising from the operation and dismantling of nuclear reactors and post irradiation examination (PIE) facilities. Two destinations of the cleared materials, namely disposal and recycle/reuse, were considered. Deterministic calculation models were established to assess individual doses resulting from 73 exposure pathways, and realistic parameter values were selected considering the Japanese natural and social conditions. The clearance levels for 21 radionuclides of nuclear reactors and for 49 of PIE facilities were derived as radioactivity concentration equivalent to the individual doses of 10 
Sv/y. Most of calculated clearance levels were nearly the same as those shown in IAEA-TECDOC-855. Some, however, were different. It is considered that the major reasons depend on differences of fixed scenarios and of selected values of parameters.
Kobayashi, Hideo
Genshiryoku Nenkan 2001/2002-Nen Ban, p.103 - 105, 2001/11
no abstracts in English
JNC TN1400 2001-015, 509 Pages, 2001/10
JNC-TN1400-2001-015.pdf:25.67MB
no abstracts in English
Nishiza, Masahiro
Genshiryoku Nenkan 2000/2001-Nen Ban, p.104 - 106, 2000/10
no abstracts in English
Okoshi, Minoru
Radioisotopes, 48(6), p.407 - 420, 1999/06
no abstracts in English
Okoshi, Minoru; Takahashi, Tomoyuki*; Kimura, Hideo; ; Sakai, Akihiro; Yoshimori, Michiro; Yamamoto, Hideaki
Hoken Butsuri, 34(2), p.187 - 197, 1999/00
no abstracts in English
Tanaka, Mitsugu; Okoshi, Minoru
Proceedings of Joint NEA/IAEA/EC Workshop on the Regulatory Aspects of Decommissioning, 3A, p.141 - 146, 1999/00
no abstracts in English
PNC TN1420 91-002, 76 Pages, 1990/01
An annual plan of FBR safety research had been made since 1986 by Japanese Nuclear Safety Commission. This plan focuses on the safety philosophy which fully utilizes the intrinsic characteristics of FBRs and which implements the safety technologies of FBRs. Items examined for establishing the safety philosophy includes : * defense-in-depth * safety grade classification * multi-barriers against radioactivity, and * severe accidents. In selecting research items, the following four fields of research were identified in relation to the safety philosophy : 1) research relating to safety design and safety evaluation principles,2) research on accident prevention and mitigation,3) research on (design basis) accidents evaluation, and 4) research on severe accidents. ATR safety research plan has been also revisedz. Its three research fields are 1) research on normal operations and anticipated operational occurrences, 2) research on accident conditions, and 3) research on severe accidents. T
Nakamura, Hideo
no journal, ,
no abstracts in English
